IR 05000334/2024010: Difference between revisions

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{{Adams
{{Adams
| number = ML24232A192
| number = ML24136A062
| issue date = 08/20/2024
| issue date = 05/15/2024
| title = Comprehensive Engineering Team Inspection - Inspection Report 05000334/2024010 and 05000412/2024010
| title = Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000334/2024010 and 05000412/2024010
| author name = Gray M
| author name = Gray M
| author affiliation = NRC/RGN-I/DORS
| author affiliation = NRC/RGN-I/DORS
Line 11: Line 11:
| contact person =  
| contact person =  
| document report number = IR 2024010
| document report number = IR 2024010
| document type = Inspection Report, Letter
| document type = Inspection Plan, Letter, Request for Additional Information (RAI)
| page count = 1
| page count = 1
}}
}}
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=Text=
=Text=
{{#Wiki_filter:August 20, 2024
{{#Wiki_filter:May 15, 2024


==SUBJECT:==
Barry Blair Site Vice President Vistra Operations Company, LLC Beaver Valley Power Station P.O. Box 4 - Route 168 Shippingport, PA 15077- 0004
BEAVER VALLEY POWER STATION, UNITS 1 AND 2 - COMPREHENSIVE ENGINEERING TEAM INSPECTION - INSPECTION REPORT 05000334/2024010 AND 05000412/2024010
 
SUBJECT: BEAVER VALLEY POWER STATION, UNITS 1 AND 2 - INFORMATION REQUEST FOR QUADRENNIAL BASELINE COMPREHENSIVE ENGINEERING TEAM INSPECTION; NOTIFICATION TO PERFORM INSPECTION 05000334/2024010 AND 05000412/2024010


==Dear Barry Blair:==
==Dear Barry Blair:==
On August 1, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Beaver Valley Power Station, Units 1 and 2 and discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region I staff will conduct a Comprehensive Engineering Team Inspection (CETI) at Beaver Valley Power Station, Units 1 and 2. Paul Cataldo, a Senior Reactor Inspector from the NRCs Region I Office, will lead the inspection team. The inspection will be conducted in accordance with Inspection Procedure 71111.21M, Comprehensive Engineering Team Inspection (CETI),
dated January 1, 2023 (ADAMS Accession No. ML19084A0 30). This inspection combines elements of the Design Basis Assurance Inspection (Teams), the Heat Exchanger/Sink Performance inspection (71111.07T), and the Evaluations of Changes, Tests and Experiments inspection (71111.17).
 
The inspection will evaluate the capability of risk-significant/low-margin components to function as designed to support proper system operation. The inspection will also include a review of selected modifications, operating experience, and as applicable, operator actions.
 
In a tele phone call between Paul Cataldo and Hope Gilliam, Beaver Valley Regulatory Compliance, on May 8, 2024, we confirmed arrangements for an information-gathering and the two-week onsite inspection. The schedule is as follows:
* Information-gathering week: Week of June 17, 2024
* Onsite weeks: Weeks of July 15, 2024, and July 29, 2024
 
The purpose of the information-gathering week is to have discussions with members of your staff to identify risk -significant components, modifications, operator actions, and operating experience items. Information and documentation needed to support the inspection will also be identified. Carey Bickett, a Region I Senior Risk Analyst, will support Paul Cataldo during the information-gathering week to review probabilistic risk assessment data and identify components to be examined during the inspection.
 
Experience with previous baseline design/modification inspections of similar depth and length has shown this type of inspection is resource intensive, both for the NRC inspectors and the licensee staff. To minimize the inspection impact on the site and to ensure a productive inspection for both parties, we have enclosed a request for information needed for the inspection.
 
It is important that all of these documents are up-to-date and complete in order to minimize the number of additional documents requested during the preparation and/or the onsite portions of the inspection. Insofar as possible, this information should be provided electronically to the lead inspector. The information request has been divided into two groups:
* The first group lists information necessary for our initial inspection scoping activities.
 
This information should be provided to the lead inspector by June 7, 2024. By June 24, 2024, the lead inspector will communicate the initial selected set of components, modifications, 50.59 screenings, and operating experience samples.
* The second group of documents requested is those items needed to support our in-office preparation and on-site activities. This set of documents, specific to the selected components and modifications, should be provided to the lead inspector no later than July 8, 2024. During the in-office preparation activities, the team may identify additional information needed to support the inspection, and those items will be communicated directly to Hope Gilliam, and selected points-of-contact identified by Hope, to facilitate the requests.


No findings or violations of more than minor significance were identified during this inspection.
If there are any questions about the inspection or the material requested in the enclosure, please contact the lead inspector at ( 610) 337-5365 or via email at pcc1@nrc.gov.


This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, Control Number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget Control Number. This letter and its enclosure will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, Public Inspections, Exemptions, Requests for Withholding.


Sincerely, Mel Gray, Chief Engineering Branch 1 Division of Operating Reactor Safety
Sincerely, Mel Gray, Chief Engineering Branch 1 Division of Operating Reactor Safety
Line 34: Line 53:
Docket Nos. 05000334 and 05000412 License Nos. DPR-66 and NPF-73
Docket Nos. 05000334 and 05000412 License Nos. DPR-66 and NPF-73


===Enclosure:===
Enclosure:
As stated
Document Request for Comprehensive Engineering Team Inspection
 
cc w/encl: Distribution via ListServ SUBJECT: BEAVER VALLEY POWER STATION, UNITS 1 AND 2 - INFORMATION REQUEST FOR QUADRENNIAL BASELINE COMPREHENSIVE ENGINEERING TEAM INSPECTION; NOTIFICATION TO PERFORM INSPECTION 05000334/2024010 AND 05000412/2024010 MAY 15, 2024
 
DISTRIBUTION:
MYoung, DORS NWarnek, DORS SElkhiamy, DORS AChristiano, DORS SBruneau, DORS NDay, DORS, SRI ANugent, DORS, RI MEvans, DORS, AA CFragman, DORS, AA FGaskins, RI OEDO RidsNrrPMBeaverValley Resource RidsNrrDorlLpl1 Resource
 
DOCUMENT NAME: https://usnrc.sharepoint.com/teams/Region-I-EB1/Documents/Inspections/CETI/Beaver Valley/Beaver Valley CETI Document and Information Request.docx ADAMS ACCESSION NUMBER: ML24136A062 SUNSI Review n -Sensitive Publvlle
 
Sensitive n -Publiclyvlable
 
OFFICE RI/DORS /
ME PC MGray TE 15/2024 15/2024 OFFIAL RERD CO DOCUMENT REQUEST FOR COMPREHENSIVE ENGINEERING TEAM INSPECTION
 
Onsite Inspection Dates: July 15, 20 24 through July 19, 2024; and July 29, 20 24 through August 2, 2024
 
Inspection Procedure: Inspection Procedure 71111.21M, Comprehensive Engineering Team Inspection (CETI)
 
Lead Inspector: Paul Cataldo, Senior Reactor Inspector PCC1@nrc.gov (610) 337-5365
 
Inspection Report: 05000334/2024010 and 05000412/2024010
 
I. Information Requested for Sample Selection Process
 
The following information is requested by June 7, 2024, to facilitate inspection preparation.
 
Feel free to contact the lead inspector as soon as possible if you have any questions regarding this information request. Please provide the information electronically in PDF files, Word, Excel, or other searchable format. The files should contain descriptive names, and be indexed to facilitate ease of use; and, if possible, identifiable using the query function in eDocs. Information in lists should contain enough information to be easily understood by someone who has knowledge of light water reactor technology.
 
1. The site probabilistic risk analysis (PRA) System Notebook and latest PRA Summary Document for both units.
 
2. Risk ranking of top 250 basic events sorted by Risk Achievement Worth (>/= 1.3) for both units. Include values for Risk Reduction Worth, Birnbaum Importance, and Fussell-Vesely (as applicable). Please provide in an Excel spreadsheet or other suitable format and include an understandable definition of the coded basic events.
 
3. Risk ranking of top 100 components from site specific PRA, sorted by Large Early Release Frequency for both units.
 
4. If you have an External Events PRA Model, provide the information requested in Item 2 for external events for both units. Provide narrative description of each coded event, including flood zone description.
 
5. List of time-critical and/or risk-significant operator actions for both units.
 
6. List of emergency and abnormal operating procedures for both units.
 
7. If available, any pre-existing evaluation or list of components and associated calculations with low design margins (e.g., pumps closest to the design limit for flow or pressure, diesel generator close to design required output, heat exchangers close to rated design heat removal) for both units.
 
8. If applicable, copy of any self-assessments and/or Quality Assurance assessments of low-margin structures, systems, and components (SSCs), completed in the last 3 years.
 
Enclosure 9. List of available design margins in both the open and closed direction for valves in the motor-operated valve (MOV) and air-operated valve (AOV) programs (related to GL 96-05, looking for resultant output - matrix of risk vs margin for MOVs and AOVs, as applicable) for both units.
 
10. The age and capacity of the safety-related batteries for both units.
 
11. The In-Service Testing Program (IST) Basis document identifying the in-scope valves and pumps, and the associated IST Program requirements for each component (e.g.,
IST valve table identifying category, active/passive function) for both units.
 
12. Listing of Maintenance Rule (a)(1) systems, date entered into (a)(1) status, and brief description of why (a)(1).


==Inspection Report==
13. List of maintenance rule functional failure (MRFF)/maintenance preventable functional failure (MPFF) evaluations completed since November 2020 (include those determined not to be a MRFF/MPFF ).
Docket Numbers: 05000334 and 05000412


License Numbers: DPR-66 and NPF-73
14. A copy of the most recent System Health and/or trending reports for the following systems (as applicable):
* Unit 1
* Class 1E 4.16KV distribution, Class 1E 480/120 VAC distribution, River Water/Service Water, Class 1E 125 VDC System, Auxiliary Feedwater System, Safety Injection (High and Low Pressure) Systems, Ch emical and Volume Control S ystems, Containment/Quench Spray System, Recirculation Spray System, Component Cooling Water S ystem, Alternate AC Source and Emergency Diesel Generators.
* Unit 2
* Class 1E 4.16KV distribution, Class 1E 480/120 VAC distribution, Service Water System, Class 1E 125 VDC, Auxiliary Feedwater System, Safety Injection (High and Low Pressure) Systems, Chemical and Volume Control System, Containment/Quench Spray System, Residual Heat Removal System, Component Cooling Water System, Alternate AC Source and Emergency Generators.


Report Numbers: 05000334/2024010 and 05000412/2024010
15. A copy of the most recent Program Health and/or trending reports for the following programs, as applicable: GL 89-10 (MOVs), GL 89-13, IST, AOVs, breakers, relays.


Enterprise Identifier: I-2024-010- 0025
16. List of open operability evaluations for both units.


Licensee: Vistra Operations Company, LLC
17. List of Root Cause Evaluations associated with SSC failures or designissues initiated/completed since November 2020.


Facility: Beaver Valley Power Station, Units 1 and 2
18. List of permanent plant modifications to SSCs that are field work complete since November 2020. For this inspection, permanent plant modifications include permanent:
plant changes, design changes, set point changes, equivalency evaluations, suitability analyses, and commercial grade dedications. The list should contain the number of


Location: Shippingport, PA
each document, title (sufficient to understand the purpose of the modification),
revision/date, and the affected system.


Inspection Dates: July 15, 2024 to August 1, 2024
19. List of calculation changes (including new calculations) that have been issued for use since November 2020.


Inspectors: J. Brand, Senior Reactor Inspector P. Cataldo, Senior Reactor Inspector J. Lilliendahl, Senior Emergency Response Coordinator K. Mangan, Senior Reactor Inspector D. McHugh, Reactor Inspector J. Schoppy, Senior Reactor Inspector A. Turilin, Reactor Inspector
20. List of corrective action documents initiated since November 2020, that address permanent plant modifications and/or 50.59 issues, concerns, or processes.


Approved By: Mel Gray, Chief Engineering Branch 1 Division of Operating Reactor Safety
21. A copy of any internal or external self-assessments performed in preparation for this inspection.


Enclosure
22. Updated Final Safety Analysis Report, Technical Specifications, and Technical/Licensing Requirements Manual for both units.


=SUMMARY=
23. Electrical simple one-line drawings for Units 1 and 2 - f rom offsite power to 4.16KV and 125 VDC.
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a comprehensive engineering team inspection at Beaver Valley Power Station, Units 1 and 2, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.


===List of Findings and Violations===
24. A list of NRC Part 21 Reports, determined to be applicable to the Beaver Valley Units 1 and 2 since November 2020.
No findings or violations of more than minor significance were identified.


===Additional Tracking Items===
25. List of all 50.59 applicability reviews, screenings, and evaluations completed since November 2020. [Note: if six or less 50.59 safety evaluations, please include electronic copies of all evaluations.]
None.


=INSPECTION SCOPES=
26. Copy of Beaver Valleys most recent Changes, Test, and Experiments summary report
[50.59(d)(2)] for both units.


Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html.
27. Copies of Fleet/Plant Program documents and procedures for the following: In-Service Testing, Maintenance Rule, Operating Experience, Corrective Action Program, Material Degradation, Self-Assessments, River Water and Service Water Reliability (GL-89-13),
Surveillance Frequency Control Program, Time-Critical and Time-Sensitive Operation Actions, and Engineering Changes or applicable Design Control (10 CFR 50, Appendix B, Criterion III) including post-modification testing, setpoint changes, associated 10 CFR 50.59 applicability/screening/evaluation procedures, and commercial grade dedications.


Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
II. Information Requested to Be Available by July 8, 20 24


==REACTOR SAFETY==
This information should be separated for each selected component and modification, especially if provided electronically (e.g., a folder for each component and modification named after the component or modification that includes the information requested below).
===71111.21M - Comprehensive Engineering Team Inspection


The inspectors evaluated the following components and listed applicable attributes, permanent modifications, Title 10 of the Code of Federal Regulations ( 10 CFR) 50.59 screening and/or evaluations, and operating experience:
Items 1 through 11 are associated with the selected components, Item 12 is for the selected modifications, and Item 13 is associated with screens/evaluations.


Structures, Systems, and Components (SSCs) (IP section 03.01) (10 Samples)
1. List of corrective action documents associated with each selected component for the last three years.


For each component or operator action sample listed below, the team reviewed licensing and design basis documents and a sampling of applicable operator actions, periodic testing results, corrective action program documents, internal and external operating experience, preventive and corrective maintenance work orders, modifications, and aging management programs. Additionally, the team performed walkdowns of the component or procedure and conducted interviews with licensee personnel.
2. Maintenance history (e.g., corrective, preventive, and elective) associated with each selected component for the last five years. Identify frequency of preventive maintenance activities.


The team used the attributes contained in IP 71111.21M, Appendix A, Component Review Attributes, such as those listed below as guidance.
3. Aging Management Program documents applicable to each selected component.


Specifically, the team evaluated these attributes as per 71111.21M, Appendix B, Component Design Review Considerations and 71111.21M, Appendix C, Component Walkdown Considerations.
4. List of calculations associated with each selected component, excluding data files. Pipe stress calculations are excluded from this request.
: (1) Risk significant operator action - Unit 1 weather-related Loss-of-Offsite Power
* Energy sources (fuel, air, steam, electricity), including those used for control functions, will be available and adequate during accident/event conditions.
* Component controls will be functional and provide desired control during accident/event conditions.
* Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.
* Instrumentation and alarms are available to operators for making necessary decisions.
* Components installed configuration will support its design basis function under accident/event conditions.
* Component operation and alignments are consistent with design and licensing basis assumptions.
* Design bases and design assumptions have been appropriately translated into design calculations and procedures.
* Potential degradation is monitored or prevented.
* Equipment is adequately protected from environmental hazards.
: (2) Unit 1 Power-Operated Relief Valve, 1-PCV-1RC-456
* Air and n itrogen will be available and unimpeded during accident/event conditions.
* Air, nitrogen, and electric, including those used for control functions, will be available and adequate during accident/event conditions.
* Component controls will be functional and provide desired control during accident/event conditions.
* Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.
* Heat will be adequately removed from major components.
* Components installed configuration will support its design basis function under accident/event conditions.
* Component operation and alignments are consistent with design and licensing basis assumptions.
* Design bases and design assumptions have been appropriately translated into design calculations and procedures.
* Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.
* Tests and/or analyses validate component operation under accident/event conditions.
* Potential degradation is monitored or prevented.
* Equipment qualification is suitable for the environment expected under all conditions.
* Equipment is adequately protected from environmental hazards.
* Component inputs and outputs are suitable for application and will be acceptable under accident/event conditions.
* Performance capability of selected components have not been degraded through modifications.
: (3) Unit 1 Recirculation Spray Heat Exchanger "1D," River Water Inlet Isolation Valve, MOV-1RW-104D
* Process medium (water, air, electrical signal) will be available and unimpeded during accident/event conditions.
* Energy sources (fuel, air, steam, electricity), including those used for control functions, will be available and adequate during accident/event conditions.
* Component controls will be functional and provide desired control during accident/event conditions.
* Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.
* Instrumentation and alarms are available to operators for making necessary decisions.
* Components installed configuration will support its design basis function under accident/event conditions.
* Component operation and alignments are consistent with design and licensing basis assumptions.
* Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.
* Tests and/or analyses validate component operation under accident/event conditions.
* Potential degradation is monitored or prevented.
* Equipment qualification is suitable for the environment expected under all conditions.
* Equipment is adequately protected from environmental hazards.
* Component inputs and outputs are suitable for application and will be acceptable under accident/event conditions.
* Performance capability of selected components have not been degraded through modifications.
: (4) Unit 1 Quench Spray Pump, 1QS-P1A
* Process medium (water) will be available and unimpeded during accident/event conditions.
* Energy sources (electricity), including those used for control functions, will be available and adequate during accident/event conditions.
* Component controls will be functional and provide desired control during accident/event conditions.
* Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.
* Instrumentation and alarms are available to operators for making necessary decisions.
* Heat will be adequately removed from major components.
* Components installed configuration will support its design basis function under accident/event conditions.
* Component operation and alignments are consistent with design and licensing basis assumptions.
* Design bases and design assumptions have been appropriately translated into design calculations and procedures.
* Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.
* Tests and/or analyses validate component operation under accident/event conditions.
* Potential degradation is monitored or prevented.
* Equipment is adequately protected from environmental hazards.
* Component inputs and outputs are suitable for application and will be acceptable under accident/event conditions.
* Performance capability of selected components have not been degraded through modifications.
: (5) Unit 1 Safety-Related 125 VDC Battery, No. 1-2 (Bus 1-2)
* Process medium (water, air, electrical signal) will be available and unimpeded during accident/event conditions.
* Energy sources (fuel, air, steam, electricity), including those used for control functions, will be available and adequate during accident/event conditions.
* Component controls will be functional and provide desired control during accident/event conditions.
* Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.
* Components installed configuration will support its design basis function under accident/event conditions.
* Component operation and alignments are consistent with design and licensing basis assumptions.
* Design bases and design assumptions have been appropriately translated into design calculations and procedures.
* Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.
* Tests and/or analyses validate component operation under accident/event conditions.
* Potential degradation is monitored or prevented.
* Equipment qualification is suitable for the environment expected under all conditions.
* Component inputs and outputs are suitable for application and will be acceptable under accident/event conditions.
: (6) Unit 2 Emergency Diesel Generator, 2-2
* Process medium (water, air, electrical signal) will be available and unimpeded during accident/event conditions.
* Energy sources (fuel, air, steam, electricity), including those used for control functions, will be available and adequate during accident/event conditions.
* Component controls will be functional and provide desired control during accident/event conditions.
* Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.
* Instrumentation and alarms are available to operators for making necessary decisions.
* Heat will be adequately removed from major components.
* Installed configuration will support its design basis function under accident/event conditions.
* Component operation and alignments are consistent with design and licensing basis assumptions.
* Design bases and design assumptions have been appropriately translated into design calculations and procedures.
* Performance capability of selected components have not been degraded through modifications.
* Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.
* Tests and/or analyses validate component operation under accident/event conditions.
* Potential degradation is monitored or prevented.
* Equipment qualification is suitable for the environment expected under all conditions.
* Equipment is adequately protected from environmental hazards.
: (7) Unit 2 Low Head Safety Injection Pump, 2SIS-P21A
* Process medium (water, air, electrical signal) will be available and unimpeded during accident/event conditions.
* Energy sources (fuel, air, steam, electricity), including those used for control functions, will be available and adequate during accident/event conditions.
* Component controls will be functional and provide desired control during accident/event conditions.
* Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.
* Instrumentation and alarms are available to operators for making necessary decisions.
* Heat will be adequately removed from major components.
* Components installed configuration will support its design basis function under accident/event conditions.
* Component operation and alignments are consistent with design and licensing basis assumptions.
* Design bases and design assumptions have been appropriately translated into design calculations and procedures.
* Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.
* Tests and/or analyses validate component operation under accident/event conditions.
* Potential degradation is monitored or prevented.
* Equipment qualification is suitable for the environment expected under all conditions.
* Equipment is adequately protected from environmental hazards.
* Component inputs and outputs are suitable for application and will be acceptable under accident/event conditions.
* Performance capability of selected components have not been degraded through modifications.
: (8) Unit 2 Charging Pump, 2CHS-P21A
* Process medium (water, air, electrical signal) will be available and unimpeded during accident/event conditions.
* Energy sources (fuel, air, steam, electricity), including those used for control functions, will be available and adequate during accident/event conditions.
* Components installed configuration will support its design basis function under accident/event conditions.
* Component operation and alignments are consistent with design and licensing basis assumptions.
* Design bases and design assumptions have been appropriately translated into design calculations and procedures.
* Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.
* Tests and/or analyses validate component operation under accident/event conditions.
* Potential degradation is monitored or prevented.
* Equipment is adequately protected from environmental hazards.
: (9) Unit 2 Turbine-Driven Auxiliary Feedwater Pump, 2FWE-P22
* Water will be available and unimpeded during accident/event conditions.
* Steam supply will be available and adequate during accident/event conditions.
* Component controls will be functional and provide desired control during accident/event conditions.
* Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.
* Heat will be adequately removed from major components.
* Components installed configuration will support its design basis function under accident/event conditions.
* Component operation and alignments are consistent with design and licensing basis assumptions.
* Design bases and design assumptions have been appropriately translated into design calculations and procedures.
* Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.
* Tests and/or analyses validate component operation under accident/event conditions.
* Potential degradation is monitored or prevented.
* Equipment is adequately protected from environmental hazards.
* Component inputs and outputs are suitable for application and will be acceptable under accident/event conditions.
* Performance capability of selected components have not been degraded through modifications.
: (10) Unit 2 Recirculation Spray Heat Exchanger, 2RSS-E21B
* Process medium (water, air, electrical signal) will be available and unimpeded during accident/event conditions.
* Operating procedures (normal, abnormal, or emergency) are consistent with operator actions for accident/event conditions.
* Instrumentation and alarms are available to operators for making necessary decisions.
* Heat will be adequately removed from major components.
* Components installed configuration will support its design basis function under accident/event conditions.
* Component operation and alignments are consistent with design and licensing basis assumptions.
* Design bases and design assumptions have been appropriately translated into design calculations and procedures.
* Acceptance criteria for tested parameters are supported by calculations or other engineering documents to ensure that design and licensing bases are met.
* Tests and/or analyses validate component operation under accident/event conditions.
* Potential degradation is monitored or prevented.
* Equipment qualification is suitable for the environment expected under all conditions.
* Equipment is adequately protected from environmental hazards.
* Component inputs and outputs are suitable for application and will be acceptable under accident/event conditions.
* Performance capability of selected components have not been degraded through modifications.


Modifications (IP section 03.02)===
5. System Health Report (last completed) and Design Basis Documents associated with each selected component.
{{IP sample|IP=IP 71111.21|count=5}}
: (1) Unit 1 EC-20-0012-002: Overload Heater Replacement for MCC-1-41-1M
: (2) Unit 1 EC-21-0022-001: Upgrade MCC-1-1-Q Cutler Hammer Components
: (3) Unit 1 EC-24-1071: WR-89 Slip-on Flange Installation for Repair
: (4) Unit 2 EC-22-1072-001: Thermal Shield Support Block Bolt Bore Internal Thread Staking
: (5) Unit 2 EC-22-1046-001: Through-wall Defect Removal, Line BV-WR-20-151-Q3


10 CFR 50.59 Evaluations/Screening (IP section 03.03) ( 10 Samples)
6. Access to or copy of vendor manual(s) for each selected component.
: (1) 18-00478: Implementation of License Amendment /Setting Changes for BV1 Degraded Voltage and Loss of Voltage Protection
: (2) 22-0086-001/2/3: Piping Material Change Downstream of Unit 1 AFWP Restricting Orifices
: (3) 22-0073-001/002: U1 Diesel Tank Level Setpoint Change
: (4) 22-1073-001: Tubing Downstream of 1RC-272 Support Relocation
: (5) 22-1076-001: Installation of Permanent Shielding at 1SW-24
: (6) 22-0049-001/002/003: Pressure Switch Setpoint Changes for U1 FWIV HYV-1FW-100A/B/C
: (7) 20-0117-001: Replace U2 SWS Emergency Diesel Generator Heat Exchanger Inlet Valves
: (8) 21-0077-001: Protect Fire Protection Lines from Future Wear
: (9) Unit 2, PAF-17-00193/Screen 17-00374/16-00913: Associated with CR-2023-05501
: (10) 50.59 associated with Compensatory Measure to Maintain Operability for U2 RWST 2QSS-TK21, from CR-2023-06404


===Operating Experience Samples (IP section 03.04) (3 Samples)===
7. List of open temporary modifications associated with each selected component, if applicable.
: (1) NRC IN 2020-04: Operating Experience Regarding Failure of Fire Protection Main Yard Piping
: (2) NRC IN 2021-03: Operating Experience Related to DAEC Derecho Event on August 10, 2020
: (3) NRC IN 2023-01: Risk Insights for High Energy Arcing Faults Operating Experience and Analyses


==INSPECTION RESULTS==
8. Trend data/graphs on the selected components performance for the last three years (e.g., pump performance including IST, other vibration monitoring, oil sample results).
No findings were identified.


==EXIT MEETINGS AND DEBRIEFS==
9. List of normal operating and alarm response procedures associated with each selected component.
The inspectors verified no proprietary information was retained or documented in this report.
* On August 1, 2024, the inspectors presented the comprehensive engineering team inspection results to Barry Blair, Site Vice President, and other members of the licensee staff.


=DOCUMENTS REVIEWED=
10. Last completed tests and surveillances for each selected component performed during the last three years. For those tests and surveillances performed at a periodicity of greater than three years, provide the latest test performed.


Inspection Type Designation Description or Title Revision or
11. Schedule of surveillance testing of selected components that occur during the onsite inspection weeks.
Procedure Date
71111.21M Calculations 10080-E-048 Emergency Diesel Generator Loading with Station Blackout Revision 16
10080-N-862 Auxiliary Feedwater Pump Performance Revision 0
211-N-423 Determine the Available NPSH for Low Head Safety Revision 0
Injection (LHSI) Pumps at Design Flow
8700-DMC-3523 Quench Spray System Performance Revision 2
8700-E-202 DC System Management Battery 1-2 - Battery Charger 1-2 Revision 3
BV-10080-N-824 Recirculation Spray Heat Exchanger Inputs for MAAP Revision 1
Containment Analysis
DMC-1516 Determination of the Valve Total Required Thrust, Actuator Revision 2,
Capability and Margin Assessment for AOVs PCV-1RC-Addendum 1
455C, D & 456
Corrective Action CR-2011-05786
Documents 2013- 00419
2017- 07594
2018- 07705
20- 04803
20- 06052
20- 08083
20- 09580
21- 08267
21- 09187
22- 00253
22- 00542
22- 01653
22- 05250
22- 05564
22- 07907
22- 08878
23- 00246
23- 01707
23- 02575
23-03005
Inspection Type Designation Description or Title Revision or
Procedure Date
23-03077
23- 03128
23- 03906
23- 04171
23- 04462
23- 05492
23- 05501
23- 05660
23- 06861
23- 09188
24- 00897
24- 00966
24- 02299
24- 02955
24- 02967
24- 02972
24- 02973
24- 03488
24- 03785
24-04511
Corrective Action CR-2024- 05832
Documents 05844
Resulting from 05850
Inspection 05884
05887
05902
05904
05917
05918
05921
05934
05935
05936
05996


Inspection Type Designation Description or Title Revision or
12. For each selected modification, copies of associated documents such as modification package, engineering changes, 50.59 screening or evaluation, relevant calculations, post-modification test packages, associated corrective action documents, design drawings, and new/revised preventive maintenance requirements.
Procedure Date
06010
06012
06040
06041
06054
06074
06164
06166
06168
06170
06192
06196
06197
201
Drawings RE-0001V 125DC One Line Diagram, Sheet 1 Revision 37
Engineering 12-04 10 CFR Part 21 Masoneilan Evaluation 12/04/2012
Evaluations EER-601419582 U1/U2 RWST Boron/Instrument Mission Time Revision 0
EER-601448014 Evaluate Out-of-Tolerance PCV-1RC-456 05/02/2024
Miscellaneous 1OST-13 Quench Spray Pump [QS-P-1A] Test 07/07/2022
1OST-13.1 Quench Spray Pump [1QS-P1A] Test 07/29/2024
1OST-47.03G Containment Isolation and ASME Sections XI Test 07/29/2024
2502.190-230- Operation and Maintenance Manual for Emergency Diesel 08/07/2019
001 Generators
2OST-11.01 LHSI Pump Full Flow Test 12/26/2023
2OST-36.2 Emergency Diesel Generator [2EGS*EG2-2] Monthly Test 06/26/2024
2OST-36.2 Emergency Diesel Generator [2EGS*EG2-2] Monthly Test 07/24/2024
2OST-36.23 EDG Simultaneous Start Test 10/30/2021
2OST-36.2A Emergency Diesel Generator [2EGS*EG2-2] 9-Hour Test 05/13/2023
NUREG-1929 Safety Evaluation Report Related to the License Renewal of October
Beaver Valley Power Station 2009
RAD/50.59 RWST Level Sensing Lines Cold Weather Protection Revision 0
Screen 23-01338 Verification
NDE Reports Eddy Current U2 RSS-E21B, 1R22 10/25/2021
Report 55140680


Inspection Type Designation Description or Title Revision or
13. A copy of the evaluation or screening document for each of the selected 50.59 evaluation/screens. A copy of the modification package if the evaluation/screen pertains to a modification.
Procedure Date
Procedures BVBP-OPS-0029 Control of Critical Actions Revision 12
NOP-OP-1013-02 Time Critical Operator Actions for Actuating CREVs Revision 0
NOP-OP-1013-02 Time Critical Operator Actions for Terminating Uncontrolled Revision 0
Charging flow to the RCS
Work Orders 200557370
200761059
200943046
200837181
200476965
200800869
200848185
200849618
200849729
200849744
200850565
200853218
200744228
200795833
200797763
200832743
200650530


14
4
}}
}}

Latest revision as of 14:40, 11 November 2024

Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000334/2024010 and 05000412/2024010
ML24136A062
Person / Time
Site: Beaver Valley
Issue date: 05/15/2024
From: Mel Gray
NRC/RGN-I/DORS
To: Blair B
Vistra Operations Company
References
IR 2024010
Download: ML24136A062 (1)
v • d • e


Text

May 15, 2024

Barry Blair Site Vice President Vistra Operations Company, LLC Beaver Valley Power Station P.O. Box 4 - Route 168 Shippingport, PA 15077- 0004

SUBJECT: BEAVER VALLEY POWER STATION, UNITS 1 AND 2 - INFORMATION REQUEST FOR QUADRENNIAL BASELINE COMPREHENSIVE ENGINEERING TEAM INSPECTION; NOTIFICATION TO PERFORM INSPECTION 05000334/2024010 AND 05000412/2024010

Dear Barry Blair:

The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)

Region I staff will conduct a Comprehensive Engineering Team Inspection (CETI) at Beaver Valley Power Station, Units 1 and 2. Paul Cataldo, a Senior Reactor Inspector from the NRCs Region I Office, will lead the inspection team. The inspection will be conducted in accordance with Inspection Procedure 71111.21M, Comprehensive Engineering Team Inspection (CETI),

dated January 1, 2023 (ADAMS Accession No. ML19084A0 30). This inspection combines elements of the Design Basis Assurance Inspection (Teams), the Heat Exchanger/Sink Performance inspection (71111.07T), and the Evaluations of Changes, Tests and Experiments inspection (71111.17).

The inspection will evaluate the capability of risk-significant/low-margin components to function as designed to support proper system operation. The inspection will also include a review of selected modifications, operating experience, and as applicable, operator actions.

In a tele phone call between Paul Cataldo and Hope Gilliam, Beaver Valley Regulatory Compliance, on May 8, 2024, we confirmed arrangements for an information-gathering and the two-week onsite inspection. The schedule is as follows:

  • Information-gathering week: Week of June 17, 2024
  • Onsite weeks: Weeks of July 15, 2024, and July 29, 2024

The purpose of the information-gathering week is to have discussions with members of your staff to identify risk -significant components, modifications, operator actions, and operating experience items. Information and documentation needed to support the inspection will also be identified. Carey Bickett, a Region I Senior Risk Analyst, will support Paul Cataldo during the information-gathering week to review probabilistic risk assessment data and identify components to be examined during the inspection.

Experience with previous baseline design/modification inspections of similar depth and length has shown this type of inspection is resource intensive, both for the NRC inspectors and the licensee staff. To minimize the inspection impact on the site and to ensure a productive inspection for both parties, we have enclosed a request for information needed for the inspection.

It is important that all of these documents are up-to-date and complete in order to minimize the number of additional documents requested during the preparation and/or the onsite portions of the inspection. Insofar as possible, this information should be provided electronically to the lead inspector. The information request has been divided into two groups:

  • The first group lists information necessary for our initial inspection scoping activities.

This information should be provided to the lead inspector by June 7, 2024. By June 24, 2024, the lead inspector will communicate the initial selected set of components, modifications, 50.59 screenings, and operating experience samples.

  • The second group of documents requested is those items needed to support our in-office preparation and on-site activities. This set of documents, specific to the selected components and modifications, should be provided to the lead inspector no later than July 8, 2024. During the in-office preparation activities, the team may identify additional information needed to support the inspection, and those items will be communicated directly to Hope Gilliam, and selected points-of-contact identified by Hope, to facilitate the requests.

If there are any questions about the inspection or the material requested in the enclosure, please contact the lead inspector at ( 610) 337-5365 or via email at pcc1@nrc.gov.

This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, Control Number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget Control Number. This letter and its enclosure will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, Mel Gray, Chief Engineering Branch 1 Division of Operating Reactor Safety

Docket Nos. 05000334 and 05000412 License Nos. DPR-66 and NPF-73

Enclosure:

Document Request for Comprehensive Engineering Team Inspection

cc w/encl: Distribution via ListServ SUBJECT: BEAVER VALLEY POWER STATION, UNITS 1 AND 2 - INFORMATION REQUEST FOR QUADRENNIAL BASELINE COMPREHENSIVE ENGINEERING TEAM INSPECTION; NOTIFICATION TO PERFORM INSPECTION 05000334/2024010 AND 05000412/2024010 MAY 15, 2024

DISTRIBUTION:

MYoung, DORS NWarnek, DORS SElkhiamy, DORS AChristiano, DORS SBruneau, DORS NDay, DORS, SRI ANugent, DORS, RI MEvans, DORS, AA CFragman, DORS, AA FGaskins, RI OEDO RidsNrrPMBeaverValley Resource RidsNrrDorlLpl1 Resource

DOCUMENT NAME: https://usnrc.sharepoint.com/teams/Region-I-EB1/Documents/Inspections/CETI/Beaver Valley/Beaver Valley CETI Document and Information Request.docx ADAMS ACCESSION NUMBER: ML24136A062 SUNSI Review n -Sensitive Publvlle

Sensitive n -Publiclyvlable

OFFICE RI/DORS /

ME PC MGray TE 15/2024 15/2024 OFFIAL RERD CO DOCUMENT REQUEST FOR COMPREHENSIVE ENGINEERING TEAM INSPECTION

Onsite Inspection Dates: July 15, 20 24 through July 19, 2024; and July 29, 20 24 through August 2, 2024

Inspection Procedure: Inspection Procedure 71111.21M, Comprehensive Engineering Team Inspection (CETI)

Lead Inspector: Paul Cataldo, Senior Reactor Inspector PCC1@nrc.gov (610) 337-5365

Inspection Report: 05000334/2024010 and 05000412/2024010

I. Information Requested for Sample Selection Process

The following information is requested by June 7, 2024, to facilitate inspection preparation.

Feel free to contact the lead inspector as soon as possible if you have any questions regarding this information request. Please provide the information electronically in PDF files, Word, Excel, or other searchable format. The files should contain descriptive names, and be indexed to facilitate ease of use; and, if possible, identifiable using the query function in eDocs. Information in lists should contain enough information to be easily understood by someone who has knowledge of light water reactor technology.

1. The site probabilistic risk analysis (PRA) System Notebook and latest PRA Summary Document for both units.

2. Risk ranking of top 250 basic events sorted by Risk Achievement Worth (>/= 1.3) for both units. Include values for Risk Reduction Worth, Birnbaum Importance, and Fussell-Vesely (as applicable). Please provide in an Excel spreadsheet or other suitable format and include an understandable definition of the coded basic events.

3. Risk ranking of top 100 components from site specific PRA, sorted by Large Early Release Frequency for both units.

4. If you have an External Events PRA Model, provide the information requested in Item 2 for external events for both units. Provide narrative description of each coded event, including flood zone description.

5. List of time-critical and/or risk-significant operator actions for both units.

6. List of emergency and abnormal operating procedures for both units.

7. If available, any pre-existing evaluation or list of components and associated calculations with low design margins (e.g., pumps closest to the design limit for flow or pressure, diesel generator close to design required output, heat exchangers close to rated design heat removal) for both units.

8. If applicable, copy of any self-assessments and/or Quality Assurance assessments of low-margin structures, systems, and components (SSCs), completed in the last 3 years.

Enclosure 9. List of available design margins in both the open and closed direction for valves in the motor-operated valve (MOV) and air-operated valve (AOV) programs (related to GL 96-05, looking for resultant output - matrix of risk vs margin for MOVs and AOVs, as applicable) for both units.

10. The age and capacity of the safety-related batteries for both units.

11. The In-Service Testing Program (IST) Basis document identifying the in-scope valves and pumps, and the associated IST Program requirements for each component (e.g.,

IST valve table identifying category, active/passive function) for both units.

12. Listing of Maintenance Rule (a)(1) systems, date entered into (a)(1) status, and brief description of why (a)(1).

13. List of maintenance rule functional failure (MRFF)/maintenance preventable functional failure (MPFF) evaluations completed since November 2020 (include those determined not to be a MRFF/MPFF ).

14. A copy of the most recent System Health and/or trending reports for the following systems (as applicable):

  • Unit 1
  • Class 1E 4.16KV distribution, Class 1E 480/120 VAC distribution, River Water/Service Water, Class 1E 125 VDC System, Auxiliary Feedwater System, Safety Injection (High and Low Pressure) Systems, Ch emical and Volume Control S ystems, Containment/Quench Spray System, Recirculation Spray System, Component Cooling Water S ystem, Alternate AC Source and Emergency Diesel Generators.
  • Unit 2
  • Class 1E 4.16KV distribution, Class 1E 480/120 VAC distribution, Service Water System, Class 1E 125 VDC, Auxiliary Feedwater System, Safety Injection (High and Low Pressure) Systems, Chemical and Volume Control System, Containment/Quench Spray System, Residual Heat Removal System, Component Cooling Water System, Alternate AC Source and Emergency Generators.

15. A copy of the most recent Program Health and/or trending reports for the following programs, as applicable: GL 89-10 (MOVs), GL 89-13, IST, AOVs, breakers, relays.

16. List of open operability evaluations for both units.

17. List of Root Cause Evaluations associated with SSC failures or designissues initiated/completed since November 2020.

18. List of permanent plant modifications to SSCs that are field work complete since November 2020. For this inspection, permanent plant modifications include permanent:

plant changes, design changes, set point changes, equivalency evaluations, suitability analyses, and commercial grade dedications. The list should contain the number of

each document, title (sufficient to understand the purpose of the modification),

revision/date, and the affected system.

19. List of calculation changes (including new calculations) that have been issued for use since November 2020.

20. List of corrective action documents initiated since November 2020, that address permanent plant modifications and/or 50.59 issues, concerns, or processes.

21. A copy of any internal or external self-assessments performed in preparation for this inspection.

22. Updated Final Safety Analysis Report, Technical Specifications, and Technical/Licensing Requirements Manual for both units.

23. Electrical simple one-line drawings for Units 1 and 2 - f rom offsite power to 4.16KV and 125 VDC.

24. A list of NRC Part 21 Reports, determined to be applicable to the Beaver Valley Units 1 and 2 since November 2020.

25. List of all 50.59 applicability reviews, screenings, and evaluations completed since November 2020. [Note: if six or less 50.59 safety evaluations, please include electronic copies of all evaluations.]

26. Copy of Beaver Valleys most recent Changes, Test, and Experiments summary report

[50.59(d)(2)] for both units.

27. Copies of Fleet/Plant Program documents and procedures for the following: In-Service Testing, Maintenance Rule, Operating Experience, Corrective Action Program, Material Degradation, Self-Assessments, River Water and Service Water Reliability (GL-89-13),

Surveillance Frequency Control Program, Time-Critical and Time-Sensitive Operation Actions, and Engineering Changes or applicable Design Control (10 CFR 50, Appendix B, Criterion III) including post-modification testing, setpoint changes, associated 10 CFR 50.59 applicability/screening/evaluation procedures, and commercial grade dedications.

II. Information Requested to Be Available by July 8, 20 24

This information should be separated for each selected component and modification, especially if provided electronically (e.g., a folder for each component and modification named after the component or modification that includes the information requested below).

Items 1 through 11 are associated with the selected components, Item 12 is for the selected modifications, and Item 13 is associated with screens/evaluations.

1. List of corrective action documents associated with each selected component for the last three years.

2. Maintenance history (e.g., corrective, preventive, and elective) associated with each selected component for the last five years. Identify frequency of preventive maintenance activities.

3. Aging Management Program documents applicable to each selected component.

4. List of calculations associated with each selected component, excluding data files. Pipe stress calculations are excluded from this request.

5. System Health Report (last completed) and Design Basis Documents associated with each selected component.

6. Access to or copy of vendor manual(s) for each selected component.

7. List of open temporary modifications associated with each selected component, if applicable.

8. Trend data/graphs on the selected components performance for the last three years (e.g., pump performance including IST, other vibration monitoring, oil sample results).

9. List of normal operating and alarm response procedures associated with each selected component.

10. Last completed tests and surveillances for each selected component performed during the last three years. For those tests and surveillances performed at a periodicity of greater than three years, provide the latest test performed.

11. Schedule of surveillance testing of selected components that occur during the onsite inspection weeks.

12. For each selected modification, copies of associated documents such as modification package, engineering changes, 50.59 screening or evaluation, relevant calculations, post-modification test packages, associated corrective action documents, design drawings, and new/revised preventive maintenance requirements.

13. A copy of the evaluation or screening document for each of the selected 50.59 evaluation/screens. A copy of the modification package if the evaluation/screen pertains to a modification.

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